US3778346A - Nuclear power station - Google Patents
Nuclear power station Download PDFInfo
- Publication number
- US3778346A US3778346A US00762185A US3778346DA US3778346A US 3778346 A US3778346 A US 3778346A US 00762185 A US00762185 A US 00762185A US 3778346D A US3778346D A US 3778346DA US 3778346 A US3778346 A US 3778346A
- Authority
- US
- United States
- Prior art keywords
- machine room
- ceiling
- reactor
- nuclear power
- power station
- Prior art date
- Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
- Expired - Lifetime
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Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C1/00—Reactor types
- G21C1/32—Integral reactors, i.e. reactors wherein parts functionally associated with the reactor but not essential to the reaction, e.g. heat exchangers, are disposed inside the enclosure with the core
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C1/00—Reactor types
- G21C1/32—Integral reactors, i.e. reactors wherein parts functionally associated with the reactor but not essential to the reaction, e.g. heat exchangers, are disposed inside the enclosure with the core
- G21C1/328—Integral reactors, i.e. reactors wherein parts functionally associated with the reactor but not essential to the reaction, e.g. heat exchangers, are disposed inside the enclosure with the core wherein the prime mover is also disposed in the vessel
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C13/00—Pressure vessels; Containment vessels; Containment in general
-
- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
Definitions
- the nuclear power station is constructed to house the reactor pressure vessel above the machine room ceiling with the ceiling being of a thin thickness. Should a leak of working medium occur in the machine room, the pressure on the ceiling of the machine room is counterbalanced -by the weight of the reactor.
- This invention relates to a nuclear power station, and particularly, to a nuclear power station housing a reactor power vessel and a machine room.
- Nuclear power stations have been constructed with a reactor pressure vessel and a pressure tight machine room for circulation of a working medium.
- the working medium is expanded in a turbine, is then cooled in a cooler, compressed in a compressor and returned to the reactor; the turbine, cooler and compressor being housed in the machine room.
- the machine room has been further constructed of dimensions to permit the working medium to expand within the machine room in the event of a leak until the pressures in the machine room and pressure vessel are equal without leakage to the exterior environment at the prevailing pressure.
- the machine room of these nuclear power stations has been built in the form of a large pressure-tight steel vessel which has also housed the reactor pressure vessel.
- this construction has been relatively expensive without making the station correspondingly safer from an escape of working medium to the exterior.
- the invention provides a nuclear reactor station with a machine room which supports a reactor pressure vessel. on the ceiling.
- the floor of the reactor pressure vessel as well as the ceiling of the machine room can thus be made relatively thin.
- the floor and ceiling can be made integral with each other.
- FIG. 1 diagrammatically illustrates one embodiment of a nuclear power station according to the invention
- FIG. 2 illustrates a cross sectional view of another embodiment of a nuclear power station according to the invention.
- FIG. 3 illustrates a view taken on line 3-3 of FIG. 2.
- a nuclear power station has a machine room 1 constructed with a floor 2 below grade, a wall 3 and a ceiling 4.
- a reactor pressure vessel15 which is of a high weight G is carried on the ceiling 4 of the machine room 1 via the floor 6 of the pressure vessel.
- the wall 3 of the machine room 1 is subjected to vertical pressure by the weight of the pressure vessel 5 bearing thereon.
- the wall 3 can be constructed of upright annular elements with circular reinforcement.
- the ceiling 4 of the machine can be constructed in such a way it also forms the floor of the reactor pressure vessel.
- the floor 6 of the reactor pressure vessel can also form the ceiling of the machine room.
- the pressure vessel floor is, in any case, highly reinforced and bend-resistant.
- the nuclear power station is housed in a single concrete structure 7.
- the concrete structure 7 contains two closed pressure-tight chambers 8, 9 which are separated by a partition 10.
- the upper chamber 7 acts as a reactor pressure chamber while the lower chamber 9 acts as a machine room.
- the partition 10 functions both as the ceiling of the machine room and as the floor of the reactor pressure chamber.
- the partition 10 also acts as a shield against radiation into the lower chamber 9.
- the reactor pressure chamber 9 contains a baflle ring 11 which carries a reactor core 12 with fuel channels 13 containing fuel rods 14.
- a heated working gas issuing from the fuel channels 13 fiows out of a central chamber 15 below the reactor core 12 through a passage 16, which passes through the partition 10, into a double-flow gas turbine 17.
- the expanded gas then flows through two passages 18 into a distributor 19. From this distributor 19, the gas passes along branch lines into a plurality of coolers 20 arranged in parallel for cooling by means of water. On leaving the coolers, the gas flows to a header 21 and thence along a duct 22 to a compressor 23.
- the gas flows along a pas sage 24 to an annular chamber 25 beneath the reactor core 12 and outside the bafile ring 11 and then up through an annular gap 26 between the core 12 and the internal wall of the pressure vessel to a distribution chamber 27 above the core 12 and back into the fuel channels 13.
- the gas turbine 17 and compressor 23 have a common shaft 28, which passes in a gas-tight manner through the machine room wall 29 and is connected outside the machine room to a turbo generator 30.
- the dimensions of the machine room are such that the product of the internal ceiling area of the lower chamber 9 and the pressure arising in the lower chamber 9 in the event of a fault is of the order of magnitude of the weight of the concrete reactor pressure vessel above the lower chamber 9. In this way, the bending stresses arising in the ceiling and floor of the lower chamber 9 remain relatively low.
- the wall 29 of the machine room is constructed of reinforced concrete and is of such dimensions as to carry the reactor pressure vessel above it and can absorb the pressure arising in the machine room in the event of a fault.
- the dimensions of the partition 10 are such as to withstand the highest pressure arising in the reactor pressure chamber 8 at the temperature which arises at the same time. Also, the partition is designed to protect the machine room sufficiently from radiation from the reactor, so that the machine room is accessible.
- the machine room can also have a door 31 or a lock in the wall 29 to permit entry into the lower chamber 9.
- a reactor power plant comprising a pressure vessel for housing a nuclear reactor core
- a pressure tight machine room mounted in pressure tight relation to said pressure vessel and housing a turbine, compressor and cooler therein" to convert thermal energy in a working medium passing from said pressure vessel into said turbine, compressor and cooler into mechanical energy and having a ceiling supporting said reactor pressure vessel, said machine room being sized to withstand the maximum pressure which may arise therein due to a leak of working medium, said ceiling being dimensioned wherein the product of the internal area of said ceiling and said maximum pressure in said machine room is of the order of magntiude of the weight of said reactor pressure vessel and the contents thereof;
- a nuclear power station comprising a reactor pressure vessel housing a reactor core, said vessel including thick radiation absorbing and pressure supporting side walls, a ceiling and a floor;
- a machine room housing thermal machine including a turbine, cooler and compressor for converting heat derived from a reactor cooling medium passing from said reactor core into mechanical energy, said machine room having a ceiling of a substantially larger area than said floor of said reactor pressure vessel with said reactor pressure vessel constituting at least a part of said ceiling of said machine room;
- a nuclear power station comprising a single structure containing two closed pressure-tight vertically disposed chambers and a partition separating said chambers, said partition forming a ceiling for the lower one of said chambers and a floor for the upper one of said chambers;
- a turbine at least one cooler and a compressor mounted in said lower chamber;
- a second passage in said partition for directing the flow of working gas from said lower chamber to said upper chamber in sealed relation wherein the product of the internal area of said ceiling of said lower chamber and the pressure arising in said lower chamber in the event of a leak of working gas into said lower chamber is of the order of magnitude of the weight of said upper chamber and said reactor core.
- the date of priority is incorrect.
- the correct date is September 19, 967.
- the date of priority is incorrect.
- the correct date is September l9, l967.
Landscapes
- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Chemical & Material Sciences (AREA)
- Chemical Kinetics & Catalysis (AREA)
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
Abstract
The nuclear power station is constructed to house the reactor pressure vessel above the machine room ceiling with the ceiling being of a thin thickness. Should a leak of working medium occur in the machine room, the pressure on the ceiling of the machine room is counterbalanced by the weight of the reactor.
Description
Dec. 11, 1973 PROFOS 3,778,346
NUCLEAR POWER STATION Filed Sept. 16, 1968 2 Sheets-Sheet 1 e e L JS P f" W m i v Fly. 7
Inventor OSKA F? PROF-OS Dec. 11, 1973 O PROFOS NUCLEAR POWER STATION 2 Sheets-Sheet 2 Filed Sept. 16, 1968 A Kw 9 2 In venfor: OSKAQ PQOFOS flTTOFP/V 5 United States Patent Officc 3,778,346 Patented Dec. 11, 1973 3,778,346 NUCLEAR POWER STATION Oskar Profos, Winterthur, Switzerland, assignor to Sulzer Brothers, Ltd., Winterthur, Switzerland Filed Sept. 16,1968, Ser. No. 762,185 Claims priority, application Switzerland, Sept. 29, 1967, 13,103/ 67 Int. Cl. G21c 13/10 US. Cl. 176-60 7 Claims ABSTRACT on THE DISCLOSURE The nuclear power station is constructed to house the reactor pressure vessel above the machine room ceiling with the ceiling being of a thin thickness. Should a leak of working medium occur in the machine room, the pressure on the ceiling of the machine room is counterbalanced -by the weight of the reactor.
This invention relates to a nuclear power station, and particularly, to a nuclear power station housing a reactor power vessel and a machine room.
Nuclear power stations have been constructed with a reactor pressure vessel and a pressure tight machine room for circulation of a working medium. Generally, after leaving a reactor housed in the presure vessel, the working medium is expanded in a turbine, is then cooled in a cooler, compressed in a compressor and returned to the reactor; the turbine, cooler and compressor being housed in the machine room. The machine room has been further constructed of dimensions to permit the working medium to expand within the machine room in the event of a leak until the pressures in the machine room and pressure vessel are equal without leakage to the exterior environment at the prevailing pressure.
In some instances, the machine room of these nuclear power stations has been built in the form of a large pressure-tight steel vessel which has also housed the reactor pressure vessel. However, this construction has been relatively expensive without making the station correspondingly safer from an escape of working medium to the exterior.
Accordingly, it is an object of the invention to provide a safe, economical and compact nuclear power station.
It is another object of the invention to utilize the weight of a nuclear reactor to balance any pressure caused by working medium leakage in an associated machine room.
Briefly, the invention provides a nuclear reactor station with a machine room which supports a reactor pressure vessel. on the ceiling. The floor of the reactor pressure vessel as well as the ceiling of the machine room can thus be made relatively thin. Alternatively, the floor and ceiling can be made integral with each other.
These and other objects and advantages of the invention will become more apparent from the following detailed description and appended claims taken in conjunction with the accompanying drawings in which:
FIG. 1 diagrammatically illustrates one embodiment of a nuclear power station according to the invention;
FIG. 2 illustrates a cross sectional view of another embodiment of a nuclear power station according to the invention; and
FIG. 3 illustrates a view taken on line 3-3 of FIG. 2.
Referring to FIG. 1, a nuclear power station has a machine room 1 constructed with a floor 2 below grade, a wall 3 and a ceiling 4. In addition, a reactor pressure vessel15 which is of a high weight G is carried on the ceiling 4 of the machine room 1 via the floor 6 of the pressure vessel. During normal operation, the wall 3 of the machine room 1 is subjected to vertical pressure by the weight of the pressure vessel 5 bearing thereon. In order to support such pressure, the wall 3 can be constructed of upright annular elements with circular reinforcement.
In the event of a fault, i.e. when the working gas enters the machine room as a result of a leak, an excess pressure P arises in the machine room and acts on the ceiling 4. Because of the counter pressure due to the weight of the pressure vessel 5, only very slight bending stresses can arise in the ceiling. Since the pressure acting on the floor 2 is absorbed by the ground, this floor need not be particularly thick. Further, although partly relieved of the vertical pressure, the wall 3 is subjected to radial internal pressure which causes a variation in loading. With the annular wall construction described above, this internal pressure can easily be absorbed by the circular reinforcements, which are then subjected to tensile stress. Alternatively, the machine room can be kept low enough below grade for the ceiling and floor to be subjected almost entirely to radial tension and the wall to slight bending stress.
Alternatively, the ceiling 4 of the machine can be constructed in such a way it also forms the floor of the reactor pressure vessel. Conversely, the floor 6 of the reactor pressure vessel can also form the ceiling of the machine room. The pressure vessel floor is, in any case, highly reinforced and bend-resistant.
Referring to FIG. 2, the nuclear power station is housed in a single concrete structure 7. The concrete structure 7 contains two closed pressure- tight chambers 8, 9 which are separated by a partition 10. The upper chamber 7 acts as a reactor pressure chamber while the lower chamber 9 acts as a machine room. The partition 10 functions both as the ceiling of the machine room and as the floor of the reactor pressure chamber. The partition 10 also acts as a shield against radiation into the lower chamber 9. The reactor pressure chamber 9 contains a baflle ring 11 which carries a reactor core 12 with fuel channels 13 containing fuel rods 14.
Referring to FIGS. 2 and 3, in operation, a heated working gas issuing from the fuel channels 13 fiows out of a central chamber 15 below the reactor core 12 through a passage 16, which passes through the partition 10, into a double-flow gas turbine 17. The expanded gas then flows through two passages 18 into a distributor 19. From this distributor 19, the gas passes along branch lines into a plurality of coolers 20 arranged in parallel for cooling by means of water. On leaving the coolers, the gas flows to a header 21 and thence along a duct 22 to a compressor 23. From the compressor 23, the gas flows along a pas sage 24 to an annular chamber 25 beneath the reactor core 12 and outside the bafile ring 11 and then up through an annular gap 26 between the core 12 and the internal wall of the pressure vessel to a distribution chamber 27 above the core 12 and back into the fuel channels 13.
The gas turbine 17 and compressor 23 have a common shaft 28, which passes in a gas-tight manner through the machine room wall 29 and is connected outside the machine room to a turbo generator 30.
The dimensions of the machine room are such that the product of the internal ceiling area of the lower chamber 9 and the pressure arising in the lower chamber 9 in the event of a fault is of the order of magnitude of the weight of the concrete reactor pressure vessel above the lower chamber 9. In this way, the bending stresses arising in the ceiling and floor of the lower chamber 9 remain relatively low. The wall 29 of the machine room is constructed of reinforced concrete and is of such dimensions as to carry the reactor pressure vessel above it and can absorb the pressure arising in the machine room in the event of a fault. The dimensions of the partition 10 are such as to withstand the highest pressure arising in the reactor pressure chamber 8 at the temperature which arises at the same time. Also, the partition is designed to protect the machine room sufficiently from radiation from the reactor, so that the machine room is accessible. The machine room can also have a door 31 or a lock in the wall 29 to permit entry into the lower chamber 9.
Although the invention has been described with reference to a nuclear power station having a gaseous working medium, it may also be applied, of course, to a nuclear power station having some other working medium.
What is claimed is:
1. A reactor power plant comprising a pressure vessel for housing a nuclear reactor core;
a pressure tight machine room mounted in pressure tight relation to said pressure vessel and housing a turbine, compressor and cooler therein" to convert thermal energy in a working medium passing from said pressure vessel into said turbine, compressor and cooler into mechanical energy and having a ceiling supporting said reactor pressure vessel, said machine room being sized to withstand the maximum pressure which may arise therein due to a leak of working medium, said ceiling being dimensioned wherein the product of the internal area of said ceiling and said maximum pressure in said machine room is of the order of magntiude of the weight of said reactor pressure vessel and the contents thereof; and
a closed flow path between said pressure vessel and said turbine, compressor and cooler in said machine room for conveying the working medium in sealed relation between said pressure vessel and said machine room.
2. A nuclear power station as set forth in claim 1 wherein said reactor pressure vessel has a floor, said floor resting on said ceiling of said machine room.
3. A nuclear power station as set forth in claim 1 wherein said ceiling of said machine room is simultaneously the floor of said reactor pressure vessel.
4. A nuclear power station as set forth in claim 1 wherein said machine room and said reactor pressure vessel are housed in a single concrete structure, said structure having a partition forming said ceiling to separate said machine room and reactor pressure vessel.
5. A nuclear power station as set forth in claim 4 wherein said partition is constructed as a radiation shield.
6. A nuclear power station comprising a reactor pressure vessel housing a reactor core, said vessel including thick radiation absorbing and pressure supporting side walls, a ceiling and a floor;
a machine room housing thermal machine including a turbine, cooler and compressor for converting heat derived from a reactor cooling medium passing from said reactor core into mechanical energy, said machine room having a ceiling of a substantially larger area than said floor of said reactor pressure vessel with said reactor pressure vessel constituting at least a part of said ceiling of said machine room; and
a plurality of passages in said ceiling for conveying the reactor cooling medium between said vessel and said thermal machines in said machine room in sealed relation within a closed circuit path.
7. A nuclear power station comprising a single structure containing two closed pressure-tight vertically disposed chambers and a partition separating said chambers, said partition forming a ceiling for the lower one of said chambers and a floor for the upper one of said chambers;
a reactor core mounted in said upper chamber;
a turbine, at least one cooler and a compressor mounted in said lower chamber;
a first passage in said partition for directing a flow of working gas from said upper chamber to said turbine, cooler and compressor in said lower chamber in sealed relation; and
a second passage in said partition for directing the flow of working gas from said lower chamber to said upper chamber in sealed relation wherein the product of the internal area of said ceiling of said lower chamber and the pressure arising in said lower chamber in the event of a leak of working gas into said lower chamber is of the order of magnitude of the weight of said upper chamber and said reactor core.
References Cited UNITED STATES PATENTS 3,402,102 9/1968 Kagi 176-60 X 3,297,542 1/1967 Costes 176-60 X 3,359,175 12/1967 Arthur et a1. 176-65 X 3,070,533 12/1962 Arms et al. 17640 3,089,840 5/1963 Carter et a1. 17694 X FOREIGN PATENTS 799,212 8/1958 Great Britain 204193.32
REUBEN EPSTEIN, Primary Examiner U.S. c1. X.R. 17638, 87
UNITED STATES PATENT oFFIcE CERTIFICATE OF CURRECTEON Paten N 3.7783 16 Dated December 11, 1973 Inventor(s) I Oskal" PIOfOS It is certified that error appears in the above-identified patent and that said Letters Patent are hereby corrected as shown below:
The date of priority is incorrect. The correct date is September 19, 967.
Column 1, line 26, "presure should be pres sure--.
Signed and sealed this 9th day of April 1971;.
(SEAL) Attest:
EDHARD I-LILET CHQP JR. C. MARSHALL DANN Attesting Officer Commissioner of Patents F ORM PC3-1050 (10-69) UscOMM-DC 60376-P69 w u.s. GOVERNMENT PRINTING OFFICE was 0-366-334,
I UNITED SITATES PATENT OFFICE CERTIFICATE OF CORRECTION Patent No. 1778,3H6 Dated December 11, 1973 Inventor(s) PIOfOS It is certified that error appears in the above-identified patent and that said Letters Patent are hereby corrected as shown below:
The date of priority is incorrect. The correct date is September l9, l967.
Columri 1, line 26, "presure" should be pres sure--.
Column2, lioe 35, "9" Should be --8----.
Sigredand sealed this 9th day of April 197E.
(SEAL) Attest: I
EDWARD ILFLETCHERJ C. MARSHALL DANN Attesting Officer. Commissioner of Patents F ORM PO-IOSO (10-69) USCOMM-DC 60376-P69 v uus, GOVERNMENT PRINTING OFFICE Ion o-ass-su,
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
CH1310367A CH481458A (en) | 1967-09-19 | 1967-09-19 | Nuclear power plant |
Publications (1)
Publication Number | Publication Date |
---|---|
US3778346A true US3778346A (en) | 1973-12-11 |
Family
ID=4389323
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
US00762185A Expired - Lifetime US3778346A (en) | 1967-09-19 | 1968-09-16 | Nuclear power station |
Country Status (8)
Country | Link |
---|---|
US (1) | US3778346A (en) |
JP (1) | JPS5037359B1 (en) |
BE (1) | BE721037A (en) |
CH (1) | CH481458A (en) |
DE (1) | DE1614610B1 (en) |
ES (1) | ES358167A1 (en) |
FR (1) | FR1573792A (en) |
GB (1) | GB1210569A (en) |
Cited By (2)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US4050984A (en) * | 1972-08-23 | 1977-09-27 | Hochtemperatur-Reaktorbau Gmbh | Closed cycle gas coolant nuclear power plant |
US4080256A (en) * | 1974-10-31 | 1978-03-21 | Westinghouse Electric Corporation | Nuclear reactor apparatus |
Families Citing this family (3)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
DE2404843C2 (en) * | 1974-02-01 | 1982-12-16 | Hochtemperatur-Reaktorbau GmbH, 5000 Köln | Nuclear power plant with closed gas cooling circuit |
DE2637166C2 (en) * | 1976-08-18 | 1984-10-04 | BBC Aktiengesellschaft Brown, Boveri & Cie., Baden, Aargau | Nuclear reactor plant with closed gas cooling circuit |
DE2907674A1 (en) * | 1979-02-27 | 1980-09-04 | Hochtemperatur Reaktorbau Gmbh | Nuclear reactor - with gas turbine driving external generator on foundation joined to concrete reactor vessel |
Family Cites Families (3)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
GB795826A (en) * | 1955-08-11 | 1958-05-28 | Gen Electric Co Ltd | Improvements in or relating to nuclear reactors |
NL109065C (en) * | 1955-11-11 | |||
GB840882A (en) * | 1956-02-09 | 1960-07-13 | English Electric Co Ltd | Improvements relating to nuclear reactors |
-
1967
- 1967-09-19 CH CH1310367A patent/CH481458A/en not_active IP Right Cessation
- 1967-09-22 DE DE1967S0111966 patent/DE1614610B1/en not_active Withdrawn
-
1968
- 1968-07-31 FR FR161342A patent/FR1573792A/fr not_active Expired
- 1968-08-27 JP JP43060966A patent/JPS5037359B1/ja active Pending
- 1968-08-29 GB GB41361/68A patent/GB1210569A/en not_active Expired
- 1968-09-14 ES ES358167A patent/ES358167A1/en not_active Expired
- 1968-09-16 US US00762185A patent/US3778346A/en not_active Expired - Lifetime
- 1968-09-18 BE BE721037A patent/BE721037A/xx unknown
Cited By (2)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US4050984A (en) * | 1972-08-23 | 1977-09-27 | Hochtemperatur-Reaktorbau Gmbh | Closed cycle gas coolant nuclear power plant |
US4080256A (en) * | 1974-10-31 | 1978-03-21 | Westinghouse Electric Corporation | Nuclear reactor apparatus |
Also Published As
Publication number | Publication date |
---|---|
GB1210569A (en) | 1970-10-28 |
JPS5037359B1 (en) | 1975-12-02 |
CH481458A (en) | 1969-11-15 |
BE721037A (en) | 1969-03-18 |
FR1573792A (en) | 1969-07-04 |
DE1614610B1 (en) | 1970-10-22 |
ES358167A1 (en) | 1970-06-01 |
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